IR 05000397/1988004
| ML17279A959 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/25/1988 |
| From: | Cillis M, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17279A958 | List: |
| References | |
| 50-397-88-04, 50-397-88-4, NUDOCS 8804130009 | |
| Download: ML17279A959 (12) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report No. 50-397/88-04 Docket No. 50-397 License No.
NPF-21 Licensee:
Washington Publ'ic Power Supply System P.
0.
Box 968 Richland, Washington 99352 Facility Name:
Washington Nuclear Project No.
2 (WNP-2)
Inspection at:
WNP-2, Benton County, Washimgton Inspection Conducted:
February 22-26, 1988 M. Cillis, Senior Radiation Specialist Inspector:
Approved by:
P.
Yu as, Chief Facili s Radiological Protection Section
~Summar:
Ins ection on Februar 22-26 1988 Re ort No. 50-397/88-04 Date Signed D te Signed inspector of liquid and liquid wastes, gaseous waste system, solid wastes, including followup of previous inspection findings, and a tour of the licensee's facility.
Inspection procedures 30703, 84523, 84524, 84722, 92701 and 92702 were addressed.
Results:
Of the five areas inspected, no violations or deviations were identified.
In the areas inspected, the licensee's performance appeared adequate to accomplish their safety objectives.
Improvements were exhibited in the management of liquid and gaseous waste programs.
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DETAILS 1.
Persons Contacted
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Powers, Plant Manager Baker, Assistant Plant Manager Garvin, Manager Programs and Audits Sorensen, Manager Regulatory Programs Graybeal, HP/Chemistry Manager Larson, Manager of Radiological Programs and Instrument Control Shockley, Health Physics/Radiochemistry Support Supervisor Bradford, Health Physics Supervisor Davis, Radiochemist Pisarcik, Senior Health Physicist Meng, Chemistry Supervisor Washington, Regulatory Compliance Supervisor Allen, Assistant Health Physics Supervisor Mix, I8C Supervisor Kippies, Senior Engineer (HVAC Systems)
Chapman, Senior Health Physicist Oldfield, Supervisor of Radiological Assessment Beardsley, Shift Supervisor Landon, Maintenance Manager The inspector also met and held discussions with other members of the licensee's staff.
- Denotes attendance at exit interview conducted on February 26, 1988.
2.
Li uids and Li uid Wastes A.
Audits and Surveillances A review of audits and surveillances performed by the licensee in the subject areas addressed in this inspection report was conducted.
The following audit/surveillance reports were reviewed:
Audit Re ort No.86-362 87-398 Dated June 6, 1986 June 18, 1987
~Sub 'ect Radiological and Nonradiological Environment and Effluent Monitoring Radiological and Nonradiological Environmental and Effluent Monitoring and Control 87-420 November 24, 1987 Radioactive Process Control Program
Surveillance Re ort No.
Date
~Sub 'ect 2-86-164 February 27, 1987 Radwaste Control and Management (Storage and Shipping)
2-87-122 March 24, 1987 Control and Verification of Radwaste Vendor Operations 2-87"265 August 10, 1987 Radioactive Effluent Surveillance Testing 2-88-042 February 18, 1988 Use and Control of Radwaste Drums The audits and surveillances were conducted by the licensee guality Assurance/quality Control staff during the period of June 1986 through February 1988.
The inspector determined that the audits were performed by individuals meeting the qualifications in ANSI N45. 2. 23.
The inspector concluded that the audits and surveillances appeared to provide management with a viable tool for assessing the effectiveness of the areas that were examined.
The audits were thorough and well documented.
The inspector noted that audit and surveillance findings are resolved in a timely manner.
No violations or deviations were identified.
~Chan ee The inspector interviewed selected Chemistry and Health Physics personnel and was informed that there had been no significant changes to the liquid waste program since the last inspection.
The inspector reviewed current liquid waste processing and sampling equipment and procedures.
No equipment changes were identified.
No violations or deviations were identified.
Effluents Selected liquid batch release permits, monitor set-point calculations, sampling records and pre and post-release calculations from 1987 were reviewed.
Calculations appeared to have been made in accordance with the methodology of the Offsite Dose Calculation Manual (ODCM) and release permits were completed in accordance with plant procedures.
The data appeared to be consistent with the information included in the Semi-Annual Effluent Reports for the first and second halves of 1987.
The licensee's 1987 annual assessment of radiation dose to the most likely "Member of the Public" to show conformance with 49 CFR Part 190 was determined to be as follows:
3.12E-02 mrem - whole body 9.5E-Ol mrem - thyroid dose 5.0E-02 mrem - any other organ The inspector noted an improvement in the documentation, maintenance and retrieval of the licensee's liquid and gaseous waste program surveillance records.
Applicable liquid and gaseous waste procedures had been revised since the previous inspection.
The inspector concluded that the licensee's liquid waste program was consistent with PPM 1. 12. 1, "Radioactive Waste Management Program" and TS, Section 4.11.1 and 4.11.4.
The inspector also verified that the licensee had maintained the Post Accident Sampling System in accordance with TS, Section 6.8.4(c)
and PPM 1.11.6,
"Post Accident Sampling Program".
No significant changes had occurred in this area since the previous inspection.
The inspector noted that no abnormal or unplanned releases occurred.
since the previous inspection.
No violations or deviations were identified.
D.
Instrumentation Radioactive liquid effluent monitoring instrumentation identified in TS, Table 3.3.7. 11-1 and Table 11.5. 2 of the Final Safety Analysis Report (FSAR) was discussed with the Health Physics/Radiochemistry Support Supervisor.
Additionally, related surveillance procedures and surveillance records for 1987 and 1988 were examine'd.
The instrumentation identified in the TS and FSAR was inspected during the tours (see paragraph 7) of the licensee's facility.
The examination disclosed that the channel checks, source checks, channel functional tests and channel calibrations prescribed in TS, Table 4.3.7. 11-1, were performed at the specified frequencies.
The inspector also verified that the method for process and effluent monitor setpoint determinations was performed in accordance with the Offsite Dose Calculation Manual and plant procedures.
No violations or deviations were identified.
E.
Reactor Coolant S ecific Activit /Chemistr 1.
S ecific Activit The inspector discussed TS, Section 3/4.45, with the Chemistry Supervisor and examined surveillance records and procedures associated with the licensee's primary coolant specific activity sampling and analysis progra Measurements and analyses of reactor coolant were performed at a frequency that met and/or exceeded the requirements prescribed in TS, Table 4.4.5-1.
Measurements were performed for gross beta and gamma activity, Dose Equivalent Iodine-131 concentration, E-Bar determination, isotopic analyses of off-gas and isotopic analysis for iodine.
The values were within the limits specified in the TS and licensee procedures.
2.
~Chamiatr Surveillance procedures established for assuring the chemistry of the reactor coolant is maintained within the limits specified in TS, Table 3.4.4-1, were reviewed.
Selected surveillance records for the period of January 1987 through February 1988 were reviewed.
The inspector verified that the reactor coolant chloride, conductivity and pH levels were maintained within TS limits.
No violations or deviations were identified.
3.
Gaseous Waste S stem A.
Audits and A
raisals See paragraph 2.A herein.
No violations or deviations were identified.
B.
~Chan ea The inspector reviewed current gaseous waste processing and sampling equipment and procedures for both normal and emergency use.
No equipment changes were identified.
Procedure changes were evaluated as to their safety significance and did not appear to constitute unreviewed safety questions.
No violations or deviations were identified.
C.
Effluents Selected continuous gaseous monitoring and grab sampling records for 1987 were examined for compliance with TS, Section 4. 11 '
and Table 4. 11-2.
Additional information related to this topic is included'in paragraph 2.C of this report.
Procedures related to the management and control of gaseous effluents were also examined.
The examination disclosed that the data appeared to be consistent with the information provided in the Semi-Annual Effluent Reports for the first and second halves of 1987.
Improvements in the documentation, maintenance and retrieval of records were observed.
Procedures related to the management and contr'ol of gaseous
effluents had been upgraded since the previous inspection.
No unplanned or abnormal releases had been reported since the previous
,inspection.
No violations or deviations were identified.
D.
Instrumentation Gaseous waste monitoring instrumentation identified in Table 4.11-2 of the TS and in Table 11.5-1 of the fSAR was discussed with the licensee's staff and inspected during the tour.
Calibration records, setpoint determination procedures and records, and surveillance procedures and records were reviewed.
The calibrations and surveillances appeared to be performed at the required frequencies and the procedures seemed adequate to accomplish the requirements of the TS.
No violations or deviations were identified.
E.
Air Cleanin S
stems'urveillance records of in-place HEPA filter and iodine adsorber testing performed pursuant to TS, Sections 3.6.5.3 and 4.7.2 and surveillance procedures implemented for accomplishing the Tests were reviewed.
No violations or deviations were identified.
F.
Meteorolo ical Instrumentation An examination of the licensee's surveillance of Meteorological Monitoring Instrumentation was conducted.
The examination was conducted for the purpose of assuring that TS surveillance requirements prescribed in Section 4. 3. 7. 3 were performed at the frequencies specified in Table 4.3.7.3-1.
Applicable I8C procedures related to performing the prescribed TS survei llances were reviewed.
A tour of the meteorological tower was made.
Selected surveillance records, such as daily channel checks and calibration records, were reviewed.
The inspector witnessed the licensee's staff performing a portion of the survei llances prescribed in the TS.
The inspector concluded that the TS surveillance requirements were being satisfied.
No violations or deviations were identified.
4.
So 1 id Wastes A.
Audits and A
raisals See paragraph 2.A herei No violations or deviations were identified.
~Chan ee The inspector was informed by the Health Physics/Radiochemistry Support Supervisor (HP/RSS) that there had been no changes in the licensee s solid waste program since the last inspection.
The inspector reviewed current solid waste procedures and processing equipment.
No equipment changes were identified.
Procedure changes did not appear to constitute an unreviewed safety question.
No violations or deviations were identified.
Processin and Stora e and Dis osal of Low-Level Radioactive Waste Discussions were held with the HP/RSS and selected records and procedures related to the licensee's solid waste cdntrol program were reviewed for the purpose of verifying compliance with:
TS, Section 4. 11.3, "Solid Radioactive Waste" TS, Section 6. 13, "Process Control Program"
CFR Part 20.311,
"Transfer for Disposal and Manifests"
CFR Part 61, "Licensing Requirements for Land Disposal of Radioactive Wastes" An individual from the Chemistry/Health Physics organization, identified as the Radwaste Management Program Leader has overall responsibility for the Radioactive Waste Management Program.
A volume of approximately 4000 cubic feet of dewatered resins, having a total activity of 425 Curies, was processed and shipped for burial during the period of July 1 to December 31, 1987.
The burial containers were LSA-190 and ES-142 liners supplied by NUPAC Services.
The licensee's procedures related'to Management of Radwaste are reviewed for adequacy at least annually and/or whenever significant changes occur.
The procedures appear to provide adequate guidelines for determining waste classification and characterization and for determination of the scaling factors for the plant's waste streams.
Tours of the licensee's radioactive material storage areas were conducted during the inspection.
The HP/RSS informed the inspector that the licensee had adequate radioactive waste storage facilities.
The examination of records did not disclose any anomalous measurements, omissions, mistakes or trends.
A total of approximately 2000 cubic feet of dry active waste (DAW)
was shipped for burial in B-25 steel boxes during the period of July 1 through December 31, 1989.
The total radioactivity of the DAW was about 0'25 Curie The waste manifests for shipment of the resins and DAM were reviewed and were found to be consistent with 10 CFR Part 20.311.
No lost shipments were reported.
The inspector noted that the licensee had established a quality assurance program for the purpose of assuring compliance with 10 CFR Parts 61.55 and 10 CFR Part 61.56.
No violations or deviations were identified.
The status of followup items identified from previous inspections were examined.
The examination disclosed the following:
A.
Enforcement Items Closed Enforcement Item 87-14-01:
Procedures in Volume ll of the licensee's Plant Procedure Manual were revised to assure all personnel skin and clothiag contamination occurrences are properly documented.
The revised procedures also include provisions for assuring an appropriate dose assessment is performed for skin and clothing contamination occurrences.
This appeared adequate to prevent recurrence.
This matter is closed.
B.
Followu Items Closed Followu Item 86-38-02
The inspector verified that the licensee's actions to tag/label valves in process and effluent monitoring (PERMs) racks had been completed.
Procedures addressing the PERMs tags/labels are expected to be completed by the end of April 1988.
This matter is closed.
Closed Followu Item 86-38-04
Inspection report 50-397/86-38-04 identified that PPM 4.602.A5-3.5, did not provide sufficient information for the licensee's staff to determine what actions and reports were necessary when a plant stack high radiation area alarm annunciated and the potential for exceeding TS limits existed.
A review of PPM 4.602.A5-3. 5 disclosed the procedure had been revised.
The revision provided adequate instructions addressing the concerns identified in the inspection report.
This matter is closed.
Closed Followu Item 87-05-01:
Paragraph 5(b) of Inspection Report identified that liquid and gaseous analysis records contained anomalies.
The inspection report also identified weaknesses in supervisory reviews of liquid and gaseous analysis records and with the "acceptance criterion" established in applicable liquid and gaseous waste surveillance procedures.
The licensee's actions to resolve the observations reported in the inspection report were reviewed during the performance of the inspection documented in paragraph 2 and 3 herein.
Additionally, the inspector held discussions with the licensee's Chemistry staf The examination revealed that the licensee had revised applicable procedures and instructed personnel.
A review of selected records during this inspection disclosed that the licensee's actions appeared to be effective to prevent recurrence.
This matter is closed.
C.
Information Notices IN 0 en Information Notice IN 87-39:
The inspector verified that the licensee had received and was in the process taking action to implement a Hot Particle Control program in accordance with the recommendations discussed in IN 87-39.
The licensee's staff informed the inspector that a Hot Particle Control program was expected to be implemented in time to support the upcoming refueling outage which is scheduled to start on or about April 25, l988.
The inspector emphasized the importance of implementing the Hot Particle Program in a timely manner.
No violations or deviations were identified.
The inspector made daily tours of the Turbine, Radwaste and Reactor Buildings.
Independent radiation measurements were performed with an Eberline, Model RO-2 ion chamber survey meter, Serial Number 2694, that is due for calibration on May 21, 1988.
The following observations were made:
a 0 Work practices were consistent with the instructions provided on Radiation Work Permits and the ALARA concept as defined in licensee procedures and 10 CFR Part 20. 1(c).
No unmonitored personnel were observed in the areas toured.
b.
Continuing improvements in housekeeping were observed.
c.
Portable instruments used for air sampling and radiation detection were in current calibration.
d.
Posting and labeling practices were consistent with 10 CFR Part 20.203,
"Caution Signs, Labels, Signals and Controls."
e.
The size of various radiation area boundaries established in the Reactor Building had increased considerably from what was observed-during previous inspections.
The increase in the size of the radiation areas was attributed to increased radioactivity in overhead piping of the areas that were toured.
Additionally, the inspector was informed of a high radiation reading on the Reactor Water Cleanup line located in the Drywell which was measured at 1500 rem on contact and 200 rem at eighteen inches.
The above observations were discussed with the licensee's staff and at the exit interview.
The inspector discussed the importance of performing an engineering evaluation to determine methods for reducing and/or
removing the sources of radioactivity.
The inspector was informed that a
licensee evaluation to determine what can be done to eliminate or reduce the radiation levels on the Reactor Mater Cleanup line was in process.
The initial evaluation indicates that it might be possible to remove the high reading portion of the Reactor Mater Cleanup line.
The inspector was informed that an evaluation for reducing or removing the sources from overhead piping in the Reactor Building would be considered.
The inspector emphasized the importance of assuring positive radiological controls are implemented for each entry made into the Drywell and that actions to reduce or remove the Reactor Water Cleanup line be completed in a timely manner to support the upcoming refueling outage which is tentatively scheduled to start on or about April 25, 1988.
No violations or deviations were identified.
7.
Exit Interview The inspector met with,the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on February 26, 1988.
The scope and findings of the inspection were summarized.
The inspector informed the licensee that no violations or deviations were identified.